ML20244C243

Monthly Operating Repts for May 1989 for LaSalle County Nuclear Station,Units 1 & 2

ML20244C243
Person / Time
Site:	LaSalle
Issue date:	05/31/1989
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 8906140175
Download: ML20244C243 (21)

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.- Commonwealth Edison i LaSall3 County Nucinr Station Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761 June 10, 1989 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail' Station F1-137 Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for May, 1989.

Very truly yours, O

Diederich f.J.

fStationManager LaSalle County Station GJD/JWT/sjc Enclosure uct A. B. Davis, NRC, Region III NRC Resident Inspector LaSalle Ill. Dept. of Nuclear Safety P. Shemanski, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, AIP Coordinator, Nuclear Services J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Terry Novotney, INPO Coordinator, LaSalle Station T. A. Hammerich, Regulatory Assurance Supervisor J . W. Gieseker, Technical Staff Supervisor i

Central File 8906140175 890531 PDR ADOCK 05000373 R PDC %N l DOCUMENT ID 0043r/0031r 4l L .-.--___--_________ _ a

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l LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT MAY 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

DOCUMENT ID 0043r/0031r t 1

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TABLE OF CONTENTS I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications

2. Changes to procedures which are described in the Safety Analysis Report

3. Tests and Experiments not covered in the' Safety Analysis Report

4. Corrective Maintenance of Safety-Related Equipment

5. Completed Safety-Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS i

1. Main Steam Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel Elements I

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DOCUMENT ID 0043r/0031r

• I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit One was issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was compiled by John W. Thunstedt, telephone number (815)357-6761, extension 2463.

l DOCUMENT ID 0043r/0031r 1

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. II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE D.ny Time Event i

h 1 0000 Reactor critical, generator on-line, 1000 MWE, ramping to full power.

l 9 2030 Reduced load to 820 MWE per. Load Dispatcher.

16 0700 Increased load to 2000 MWE.

17 0700 Increased load to 1130 MWE.

19 2200 Decreased load to 675 MNE for rod-set.

l 20 0300 Increased load to 1050 MWE.

l 22 1900 Decreased load to 850 MWE for Load Dispatcher.

29 0630 Increased load to full power.

31 2400 Reactor critical, generator on-line, 1100 MWE.

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to the Facility License or Technical Specification.

(None)

2. Changes to procedures which are described in the Safety ]

l Analysis Report.

(None)

3. Tests and Experiments not described in the Safety Analysis Report.

(None)

4. Major corrective maintenance to Safety-Related Equipment.

(See Table 1)

5. Completed Safety-Related modifications.

(None) l l

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C. LICENWE EVENT REPORTS LER Numbar Date Description-89-016-00 05/02/89 Procedure DG Testing Frequency Inadequacy.

89-017-00 05/15/89 Failure of 'O' DG Cooling Water Pump Breaker.

89-018-00 05/15/89 RCIC Isolation on High Steam Line DP.

89-019-00 05/26/89 Charcoal Lab Sample Results Out of Tolerance.

89-020-00 05/29/89 Failure of 250 VDC Feed Circuit Breaker to 250 VDC Bus 121Y D. DATA TABULATIONS

'1. Operating Data Report (attached)

2. Average Daily Unit Power Level (attached)

3. Unit Shutdowns and Power Reductions (attached)

DOCUMENT ID 0043r/0031r

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• b . D.i OPERATING I,ATA REPORT DOCKET NO. 050-373 1 UNIT LASALLE ONE l' DATE Ane 10,1989 'I COMPLETED BY J.W. THUNSTEDT TELEPHDNE (015)-357-6761 q OPERATICS $TATUS l P 1..REPDRTING PERIOD: HAY 1989 GROSS HDURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIIED POWER LEVEL-(MWt): 3,323 MAX DEPEND CAPACITY (MWe-Nei): 1,036

,. DESIGN ELECTRICAL RATING (HWe-Net) .1,078 j

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3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe-Nei): (NDNE) 4..' REASONS FOR RESTRICTION (IF ANY): (N/A)

REPORTING PERIOD DATA j THIS MONTH YEAR-T04 ATE CUMULATIVE

9. VICE REACTOR CRITICAL (HOURS) 744.0 3,549.3 29,568.6

6. 'TIGE REACTOR RESERVE SHUTDOWN (HOURS): 0.0 0.0 1,641.2

7. . TIME GENERATOR ON-LINE (HDURS) 744.0 3,539.t~ 28,B53.6 l

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9.jT!PEGENERATORRESERVESHUTDOWN(HOURS) 0.0 0.0 1.0 ]

b 9.~ THERMAL ENERGY GENERATED (MWHi-Gross) 2,244,550 11,207,542 79,986,120

10. ELEC11tICAL ENERGY GENERATED (MWHe-Gross) 757,181 3,824,549 26,470,303  !

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'.11. ELECTRICAL ENERLY GENERATED (MWHe-Net) 732,247 3,688,089 25,263,6f8 j

- 12. REACTOR SERVICE FACTOR (%)~ 100.0 98.0 62.3 )

13. REACTOR AVAILABILITY FACTOR (I) 100.0 98.0 65.7 j

14. SERVICE FACTOR (%) 100.0 97.7 60.8 -l

15. AVAILABILITY FACTOR (1) 100.0 97.7 60.8 )

16. CAPACITY FACTOR (USING MDC) (%) 95.0 98.3 51.4 l: 91.3 94.4 49.4

17. EAPACITY FACTOR (USING DESIGN MWe) (%)

10. FORCED OUTAGE FACTOR (%) 0.0 2.3 10.9

19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 M3NTHS (TYPE, DATE, AND DURATION OF EACH): ) '

Refuelir.g 9-3-89 12 Weeks

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l ' 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

I- (N/A) ,

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30CKET NO. 050-373

- UNIT LASALLE ONE D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE June 10,iM 9-COMPLETED BY J.W. THUNS' D T TELEPHONE (815)-357-iii61 REPORT PERIOD: MAT 1989 DAY POWER DAY POWER i 1,060 17 1,012 2 1,088 - 18 i,000 3 1,046 19 1,660 4 -1,030 20 874 5 1,087 21 1,033 6 1,090 22 989 7 1,095 23 922 8 1 ,092 24 899

.9 1,032 25 992 10 825 26 1,005 11 827 27 1,040 12 826 28 949 13 B22 29 947 14 226 . 30 1,074 15 921 31 1,037 16 932 l

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. E,iUNIQUE REPORTING REQUIREMENTS

1. . Safety / Relief. valve operations VALVES -NO & TYPE PLANT DESCRIPTION-DATE ACTUATED ACIDATION CONDITION 0F EVENT (None) 2 .1 -ECCS System Outages-OUTAGE NO. EQUIPMENT PURPOSE-

'(Unit 0) s 0-140-89 ODG01K Replace air-start motors.

l 0-141 ODG01K Lubricate cooling-water pump.

0-151-89 ~ ODG01K Cooling-water pump Repair' feeder breaker.

(UNIT 1) 1-238-89 1A D/G. Replace air-start motors.

1-239-89' 1E12-F047B (RH) E.O. Heat-exchanger inlet.

1-240-89 .1E12-F003B (RH) E.Q. Heat-exchanger.

1-254-89 1.B D/G Air Compressor Replace head bolts.'

1-255-89 1B D/G Replace air-start motors.

1-256-89, 1B D/G Lubricate.

1-257-89 1B D/G Calibrate instrumentation.

1-267-89 1DG08CB Air Compressor Repair lube oil' leak.

1-278-89 1E12-F094 (RII) Perform surveillance.

1-280-89 RCIC Calibrate instrumentation.

1-284-89 RCIC (Administrative) 1-291-89 1E12-F312B (RH) ,spect MOV torque switch.

, 1-293-89 IE51-F010 (RI) Inspect MOV torque switch.

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l , OUTAGE NO. EOUIPMEN'S IITRPOSE UNIT 1 (CONTINUED) 296-89 RHR Service Water Pump Lubricate coupling.

l-l- 1-302-89 1B D/G Calibrate instrument.

1-303-89 IB D/G Replace var and watt meters.

1-304-89 1E12-F087B (RH) Perform surveillance.

1-309 RCIC drain pot Repair leak.

1-311-89 1E51-F022 (RI) Install motor termination kit.

1-315-89 1A RHR Pump Clean deal-oil coolor.

3. Off-Site Dose Calculation Manual (None)

4. Major changes to Radioactive Waste Treatment Systems.

(None) 5.' Indications of Failed Fuel Elements.

(None)

DOCUMENT ID 0043r/0031r

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LASALLE NUCLEAR POWER STATION UNIT 2 l

MONTHLY PERFORMANCE REPORT i l

MAY, 1989 COMMONWEALTH EDISON COMPANY i

NRC DOCKET NO. 050-374 LICENSE NO. NPF-18  !

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DOCUMENT ID 0036r/0031r 1

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TABLE OF CONTENTS l

I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications

2. Changes to procedures which are described in the Safety Analysis Report.

3. Tests and Experiments not covered in the Safety Analysis Report.

4. Corrective Maintenance.of Safety-Related Equipment

5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations

2. ECC3 System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel Elements DOCUMENT ID 0036r/0031r

=.

I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois. Each unit is a Boiling dater Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois Rive

• for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit Two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

This report was compiled by John W. Thunstedt, telephone number (815)357-6761 extension 2463.

l DOCUMENT ID 0036r/0031r

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I II. MONTHLY REPORT A.

SUMMARY

OF OPERATING EXPERIENCE Day Time Event 1 0000 Reactor critical, generator on-line, 1115 MWE.

12 2100 Reduced load to 870 MWE for TDRFP maintenance.

14 0400 Increasing load to 1125 MWE.

15 2400 Reduced load to d50 por Load Dispatcher.

16 0500 Increasing load to 1115 MWE.

31 2200 Reducing load to 830 MWE for CRD exercising and MSIV testing.

2400 Reactor critical, generator on-line, 830 MWE.

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to the Facility License or Technical Specification.

(None)

2. Changes to procedures which are described in the Safety Analysis Report.

(None)

3. Tests and Experiments not described in the Safety Analysis Report.

(None)

4. Major corrective maintenance to Safety-Related Equipment.

(None).

5. Completed Safety-Related Modifications.

(None).

DOCUMENT ID 0036r/0031r

4 C. ' LICENSEE-EVENT REPORTS l

LER Number Date Description

.(None)

D. DATA TABULATIONS

1. Operating Data Report (Attached)

2. Average Daily Unit Power Level (Attached)

3. Unit Shutdowns and Power Reductions (Attached)

DOCUMENT ID 0036r/0031r

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1- .g D.1 OPERATING DATA REPORT DOCKET NO. 050-374 i UNIT LASALLE TWO l DATE J oe 10,1989 COMPLETED BY J.W.THUNSTEDT

-TELEPHONE (815)-357-6761

OPERATING STATUS

'.t.5REPORTINGPERIODi MAY 1989 GROSS HOURS IN REPORTING PERIOD: 744 l

2.: CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 i DESIGN ELECTRICAL RATING (MWe-Net) 1,078 l

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3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe-Net): (NONE) .i 4.. REASONS FOR RESTRICTION (IF ANY): (N/A)  !

REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE  !

~ 5. TIE REACTOR CRITICAL (HOURS) 744.0 2,709.1 26,187.1  !

I 1,716.9 2

6. TIRE REACTOR RESERVE SHUTD0WN (HOURS) 0. 0 0.0

7. TIME CENERATOR DN-LINE'(HOURS) 744.0 2,657.5 25,748.5 i

8. TIGE GENERATOR RESERVE SHIJTDOWN (H3URS) 0.0 0.0 0.0

-9.- THERMAL ENERGY GENERATED (MWHt-Gross) 2,450,352 8,134,656 74,074,264 i

10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 812,599 2,697,793 24,401,131 I

11.-ELECTRICAL ENERGY GENERATED (MWHe-Net) 784,663 2,602,253 23,341,503.

12. REACTOR SERVICE FACTOR (I) 100.0 74.0 -64.7 1

13. REACTOR AVAILABILITY FACTOR (I) 100.3 74.8 69.0 14.~ SERVICE FACTOR (%) 100.0 73.4 63.6 l l

15. AVAIL!BILITY FACTOR (%) 100.0 73.4 63.6

16. CAFACITY FACTOR (USING MDC) (%) 101.8 69.3 55.7

17. CAFACITY FACTOR (USING DESIGN MWe) (I) 97.8 66.6 53.5

18. FORCED CU1 AGE FACTOR (%) 0.0 0.3 15.5 l .

l l: 19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

l~ (NONE) l l-

, 20. IF SHUIDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

l (N/A) 2

* - -* . DOCKET NO. 050-374

- UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE June 10,1989 l COMPLETED BY J.W. THtMSTEDT TELEPHONE (615)-357-6761 REPORT PERIOD: MAY 1989 DAY POWER DAY POWER-1 ~1,067 17 1,059 '

2 1,054 18 1,061 3- 1,067- 19 1,065 4 1,055 20 1,061 5 1,070 21 1,062 6 i,074 22 1,060 7 1,075 23 1,057 8 1,070 24 1,053 i

9 1,071 25 1,046 10 1,062 26 1,058 11 1,051 27 1,058 12 1,035 28 1,054

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION DEIE ACIUATED ACTUATIQt1S CONDITION OF EVENT (None)

2. ECCS System Outages OUTAGE NQ1 EOUIPMENT PURPOSE 2-544-89 2B D/G Investigate shutdown circuits.

2-553-89 2E22-C302A (DG) Torque head-bolts.

2-554-89 2B D/G Replace gauges.

2-556-89 2B D/G (Administrative).

2-564-89 RCIC Water Pump Lubricate.

2-565-89 RCIC Vacuum Pump Perform surveillance.

2-266-89 RCIC Condensate Pump Performance surveillance.

2-595-89 2A D/G Calibrate instrumentation.

2-596-89 2A D/G Replace air-start motors.

2-597-89 2A D/G Replace var and watt meters.

2-598-89 2B RHR Service Water Replace vent line.

3. Off-Site Dose Calculation Manual (None)

4. Major changes to Radioactive Waste Treabment Systems.

(None)

5. Indications of Failed Fuel Elements.

(None)

! DOCUMENT ID 0036r/0031r

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